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Quarterly report: Pumps-status of slurry pumps in coal liquefaction processes. Third quarter - CY 1981

Description: This paper summarizes recent slurry pumps (centrifugal and reciprocal) operating experience in the liquefaction pilot plants. In addition, the activities concerning slurry pumps conducted in supporting research facilities are also noted. The purpose of the summary is to concentrate on the critical component problems common to all the liquefaction plants to avoid duplication of efforts, and to help provide timely solutions to the pump problems. The summary information used in this paper was obtained primarily from the Critical Component and Materials Meetings which are sponsored by the Office of Coal Processing of the Fossil Energy. The Department of Energy. Information from various Technical Reports published by the liquefaction plant personnel are also reviewed based on availability and relevance to topics covered in this report. It is intended that this report will be followed by updates as pertinent information concerning problem pumps becomes available. The following section s of the paper will provide a brief outline of early slurry pump experience as background material followed by a summary of recent slurry pump operating experience at liquefaction pilot plants.
Date: July 1, 1996
Partner: UNT Libraries Government Documents Department

Instrumental analysis progress report, June 1--30, 1949

Description: Several bismuth compounds have been submitted by E. Orban for examination by x-ray diffraction. The sample of polonium in contact with platinum mentioned in the May progress report was received and identified tentatively from its x-ray diffraction pattern as PtPo{sub 2}. Calibration of the Perkin-Elmer infrared spectrophotometer has been completed and a preliminary study of the infrared absorption of NiCO{sub 4} made. Data showing the spectral purity obtainable on three ultraviolet-visible spectrophotometers have been completed. The emission spectrum of a sample of volatile impurity from the operations process has been obtained.
Date: December 31, 1949
Creator: Timma, D.L.
Partner: UNT Libraries Government Documents Department

Field task proposal/agreement separation and purification of radioisotopes for research

Description: The present purpose of this program is to produce high-purity uranium-234 (99%) and polonium-209 for the scientific community, both Governmental and non-Governmental. In addition, facilities for separation and purification of protactinium-231, thorium-230, and thorium-229 are maintained in stand-by condition for the resumption of these processes when conditions warrant. The uranium-234 isotope is separated from aged plutonium-238 material, purified, and converted to solid U{sub 3}O{sub 8}. This oxide is subsequently shipped to Oak Ridge National Laboratory for distribution through their Isotope Sales Group. The principal use of uranium-234, which is recovered from aged plutonium-238, is in fission detectors used to monitor reactors. Approximately one-third of the total uranium in a fission detector is uranium-234. The other two-thirds is uranium-235. A typical detector might contain 15 mg total uranium. As the neutron flux in the reactor causes fission of the uranium-235 in the detector, it also converts the uranium-234 to uranium-235.
Date: November 20, 1980
Creator: Wilkes, W.R. & Eppley, R.E.
Partner: UNT Libraries Government Documents Department

Mound Laboratory plutonium study: Presentation to the scientific review panel

Description: This paper describes the Mound plutonium study. The objectives of the project were to evaluate the inventory of plutonium 238 in the environment at Mound, determine the source, and alleviate potential health hazards. Analysis of soils, water, vegetation, fishes, and runoff were performed.
Date: February 19, 1975
Creator: Rogers, D. R.; Westendorf, W. H. & McClain, J. R.
Partner: UNT Libraries Government Documents Department

Safe TRU waste transport system

Description: The transportation of DOE`s TRU waste is highlighted in the Defense Waste Program Management Document as one of six key elements in the effective management of TRU waste. In addition, the report of Dr. Magnus` Committee on Transportation of Nuclear Materials discusses several major needs, such as: (1) Lack of shipping container standardization. (2) Lack of uniform analytical evaluation techniques in determining package performance with respect to test (performance) criteria. (3) Lack of public acceptance and understanding of safety aspects. (4) Lack of a functional transportation data base. These can be summarized by stating that a need exists for an integrated, long-term DOE Transportation Plan.
Date: October 31, 1977
Creator: Edling, D. A.
Partner: UNT Libraries Government Documents Department

GOSIP overview

Description: The U.S. Federal Government has mandated use of the International Standards Organization`s Open Systems Interconnection (OSI) protocols throughout all federal computer network services and products. A Federal Information Processing Standard (FIPS) was adopted February 15, 1989 and enforcement began August 15, 1990. This FIPS describes, in publication 146, national policy mandating use of a functional profile of OSI approved protocols relevant to the federal government. Law requires all federal agencies purchasing network services and products to specify the Government OSI Profile, called GOSIP. This standard is compulsory and binding for all procurements of new networking products and services and for major upgrades to existing computer networks. This paper provides a discussion of GOSIP.
Date: July 1, 1996
Creator: Van Norman, H.J.
Partner: UNT Libraries Government Documents Department

Acceptable TRU packaging for interim storage and/or terminal isolation

Description: The major objective of ERDA Manual Chapter 0511 is responsible technical management of its radioactive wastes. To ensure long term technical management, this DOE responsibility initially begins with the generation of radioactive wastes in all DOE operations and includes all other attributes and parameters (waste processing, packaging, shipping and storage) over the lifetime of the radionuclides. Close examination of the entire waste management cycle clearly indicates that one of the most important constituents which minimizes the risk to man and his environment is an effective and totally acceptable waste package containment system. The retrievable storage site for defense transuranic waste at the Idaho National Engineering Laboratory has been accepting waste since November, 1970. Current DWPR planning calls for continuing use of the retrievable storage pad through FY-1987 with the WIPP facility attaining full operational status in FY-1988. In the FY-1976, 76A period over 107,000 ft of transuranic wastes were stored retrievably at INEL. This volume represents approximately 4000 drums of the 7.3 ft{sup 3} (55 gal.) size and 700 4 x 4 x 8` FRP coated plywood boxes on an annualized basis. At this waste generation rate, a rate which is probably conservative based upon known decontamination and decommissioning projects at Mound, Rocky Flats, LASL, Atomics International, LBL, and ORNL which will substantially increase TRU volumes before the WIPP becomes operational a total of approximately 32,000 drums and 5600 boxes will be added to storage at INEL. Based upon the difficult decisions presently being faced with respect to the acceptability to WIPP of the waste already in storage at INEL, it is imperative not to increase this scope of the problem by continuing to use waste containers which may well not be acceptable to the terminal isolation facility.
Date: October 31, 1977
Creator: Kokenge, B.R.
Partner: UNT Libraries Government Documents Department

Tester status report: April-June 1979

Description: This report details tester status and activities in support of testing of timers, actuators, detonators, firing sets, transducers, isolators, and pyrospacers for the period of April through June 1979.
Date: August 31, 1979
Creator: Draut, C.F.
Partner: UNT Libraries Government Documents Department

Pre-operational safety appraisal Tritiated Scrap Recovery Facility, Mound facility

Description: The purpose of this report is to identify, assess, and document the hazards which are associated with the proposed operation of the Tritiated Scrap Recovery Facility at Mound Facility. A Pre-operational Safety Appraisal is a requirement as stated in Department of Energy Order 5481.1, Safety Analysis and Review System. The operations to be conducted in the new Tritiated Scrap Waste Recovery Facility are not new, but a continuation of a prime mission of Mound`s i.e. recovery of tritium from waste produced throughout the DOE complex. The new facility is a replacement of an existing process started in the early 1960`s and incorporates numerous design changes to enhance personnel and environmental safety. This report also documents the safety of a one time operation involving the recovery of tritium from material obtained by the Department of Energy from the State of Arizona. This project will involve the processing of 240,000 curies of tritium contained in glass ampoules that were to be used in items such as luminous dial watches. These were manufactured by the now defunct American Atomics Corporation, Tucson, Arizona.
Date: July 1, 1996
Creator: Dauby, J.J.; Flanagan, T.M.; Metcalf, L.W. & Rhinehammer, T.B.
Partner: UNT Libraries Government Documents Department

GOSIP implementation guidelines

Description: GOSIP (Government Open Systems Interconnection Profile) is a subset of ISO`s OSI protocol standards relevant to US Government operations. As a Federal Information Processing Standard (FIPS), GOSIP is required by law for all Federal agencies. Mandatory standards-based communications products are required when purchasing functionality equivalent to what is specified in GOSIP. This unprecedented requirement by the Federal government has caused considerable confusion concerning practical implementation of relatively immature and untested technologies. Many organizations already have substantial investment in one or more proprietary network architectures. This paper examines issues associated with conversion to the GOSIP system.
Date: July 1, 1996
Creator: Van Norman, H.J.
Partner: UNT Libraries Government Documents Department

Report for research on substitute materials. Quarterly progress report, April 2, 1951 to July 2, 1951 (Polonium-208)

Description: Mound Laboratory is cooperating on a joint development program directed toward the production of polonium-208 by proton irradiation of bismuth. Because of the greater half life of polonium-208 compared with polonium-210 (2.93 years versus 138.4 days), it would be a desirable substitute for polonium-210, At the present time the Electromagnetic Division of Oak Ridge National Laboratory is operating a cyclotron for the production of polonium-208 on an experimental scale. The targets produced are sent to Mound Laboratory for evaluation of the results which have been obtained, as well as for processing of the targets to obtain experimental amounts of the polonium in a purified form. The California Research Corporation is designing the target to be used in the Mark I linear accelerator located at Livermore, California. The overall responsibility for the Mark I design and operation is being handled by the California Research and Development Corporation. Before it is used for the production of polonium-208, the Mark I will be convert d from a deuteron beam, on which it will first operate, to a proton beam. This report describes progress on separation processes of bismuth and polonium, and diffusion of polonium through aluminium.
Date: August 6, 1951
Partner: UNT Libraries Government Documents Department

Tentative method for the determination of plutonium-239 and plutonium-238 in water (by a coprecipitation anion exchange technique)

Description: A procedure for the determination of plutonium 238 and plutonium 239 in water is described. The procedure consists of a coprecipitation, an anion exchange separation and electrodeposition, followed by alpha pulse height analysis. More specifically, the sample is acidified with nitric acid and plutonium-242 is added as a tracer before any chemical separations are performed. Iron is added to the water as iron (III) and the plutonium is coprecipitated with the iron as ferric hydroxide by adding ammonium hydroxide. After decantation and centrifugation, the ferric hydroxide precipitate containing the coprecipitated plutonium is dissolved and the solution is adjusted to 8M in HNO{sub 3} for anion exchange separation. When the sample fails to dissolve because of the presence of insoluble residue, the residue is treated by a rigorous acid dissolution using concentrated nitric acid and hydrofluoric acids. The sample is poured over an anion exchange column. The iron and most other elements that might be present pass through the column. Thorium is removed from the column with 12 M hydrochloric acid and then the plutonium is eluted by reducing it to plutonium (III) with the iodide ion. The plutonium is electrodeposited onto a stainless steel slide for counting by alpha pulse height analysis using a silicon surface barrier detector. From the recovery of the plutonium-242 tracer, the absolute amounts of plutonium-238 and plutonium-239 can be calculated, and from the volume of sample analyzed the concentrations of these two isotopes in the water sample can be calculated.
Date: September 17, 1976
Creator: Bishop, C. T.; Brown, R.; Glosby, A. A.; Phillips, C. A. & Robinson, B.
Partner: UNT Libraries Government Documents Department

Environmental monitoring summary: 1977

Description: Monsanto Research Corporation operates Mound Facility, a government-owned facility of the U.S. Department of Energy (DOE) in Miamisburg, Ohio. Mound Facility is an integrated research, development, and production facility performing work in support of DOE weapon and nonweapon programs with emphasis on explosive and nuclear technology. This report provides information on the environmental monitoring of the Mound plant for 1977.
Date: June 9, 1978
Partner: UNT Libraries Government Documents Department

Quality program plan

Description: This report describes a quality program plan for the Mound laboratory. Areas include variation engineering, technical manual process control systems, process performance data, product index system, promotional marketing program, quality engineering staff, ultimate use education, and management reporting.
Date: July 15, 1977
Creator: Kelly, D.P.
Partner: UNT Libraries Government Documents Department

Mound Facility. 1978 annual report

Description: For Mound Facility, the year 1978 was one of progress marked by enhanced mission assignments and significant milestones. The thirtieth anniversary of the site was celebrated, and Monsanto Research Corporation began a new 5 year contract to operate the Mound Facility. Long-standing production assignments were strengthened, and were were given a new responsibility: to develop and produce all ceramic parts used in Mound-build products. progress toward US energy objectives was bolstered by Mound programs supporting the development of nuclear fusion poser, unlocking previously us attainable fossil fuels, ensuring the safety and security of nuclear material handling operations, and exploring the real promise of energy form the sun. In 1978, we focused our attention on many efforts aimed at a brighter, more secure future.
Date: December 31, 1979
Partner: UNT Libraries Government Documents Department

Annual environmental monitoring summary, July 1975--June 1976

Description: Monsanto Research Corporation operates Mound Laboratory, a government-owned facility of the U.S. Energy Research and Development Administration, at Miamisburg, Ohio. Mound Laboratory is an integrated, research, development, and production facility performing work in support of ERDA weapon and nonweapon programs with emphasis on explosive and nuclear technology. Mound Laboratory originated as a technical organization in 1943 when Monsanto Chemical Company was requested to accept responsibility for determining the chemical and metallurgical properties of polonium as a project of the Manhattan Engineering District. Work was carried on at Monsanto`s Central Research Department and several satellite units in the Dayton, Ohio area. Late in 1945, the Manhattan Engineering District determined that the research, development and production organization established by Monsanto at Dayton should become a permanent facility. A search for a suitable location in early 1946 led to the selection of a 180-acre tract adjacent to Miamisburg, about ten miles (16 km) south of Dayton. Construction of Mound Laboratory, which was named after the Miamisburg Indian Mound adjacent to the site, began in February 1947 and was completed in 1948. The new laboratory was the first permanent facility of the Atomic Energy Commission which had succeeded the Manhattan Engineering District.
Date: October 29, 1976
Partner: UNT Libraries Government Documents Department

Analysis of trapped gas in 1E34 detonators by gas chromatography

Description: A method was developed to extract and then analyze gas trapped in thermally aged 1E34 detonators. This gas was extracted into an evacuated volume and injected into a gas chromatograph for separation and quantitative analysis. To effect this gas extraction, a device was designed for puncturing the detonator cup and capturing the effused gas. Limited testing of five detonators in this device shows amounts of gas ranging from about 0.5 X 10 {sup -7} to 12 X 10 {sup - 7} moles.
Date: May 14, 1980
Creator: Warner, D.K.; Back, P.S. & Barnhart, B.V.
Partner: UNT Libraries Government Documents Department

LWRHU EB weld development

Description: Electron beam weld development studies were performed for both the platinum frit vent-to-vent cap weld and also the vent cap-to-body weld for the LWRHU Project using a Hamilton Standard EBW-6 Electron Beam Welder. A total of six (6) development welds each was performed to establish welding parameters and procedures which would produce satisfactory and acceptable welds. The relatively small size of the platinum frit vent dictated that the frit-to-vent cap weld would have to be limited as to depth of penetration and also to minimize the reduction of the porous frit areas.
Date: January 22, 1980
Creator: Greene, L.A.
Partner: UNT Libraries Government Documents Department

Mound bridge-wire welding, testing and corrosion seminar, Miamisburg, OH, May 7-8, 1968

Description: Brief summaries are presented on the following presentations: welding for low voltage operation, welding techniques at Mound, welding/joining at Sandia, Ultrasonic`s plastic assemblies of detonator components, laser welding bridge-wires, laser safety in the Biorad industrial environment, nondestructive testing at Mound, thermal cycle data and evaluation, thermal cycle nondestructive testing, corrosion of detonator electrode and bridge-wire, and corrosion studies and fabrication of bridge-wire at Sigmund Cohn.
Date: August 7, 1968
Creator: Richards, M.A.
Partner: UNT Libraries Government Documents Department